Basic Studies in the Field of High-temperature Engineering [electronic resource] : Second Information Exchange Meeting
Publishing, OECD.
NEA StaffCorporate Author
Agency, Nuclear Energy.
Paris : Organisation for Economic Co-operation and Development,
2002.
In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, the NEA organised a Second Information Exchange Meeting on Basic Studies in the Field of High-temperature Engineering. These proceedings provide an overview of the activities being carried out in eight countries, the improvement of material properties for HTGR application, in-core monitoring methods and properties of irradiated graphite, and HTGR fuel fabrication and performance.
Description based upon print version of record.
Foreword; CONTENTS; Executive Summary; OPENING SESSION; Welcome Address; Opening Address; SESSION I Overviews of High-temperature Engineering Research in EachCountry and Organisation; Research Activities on Hish-Temperature Gas-cooled Reactors (HTRs) in the 5th Euration RTD Framework Programme; Update on IAEA High-Temperature Gas-cooled Reactor Activities; Present Status of the Innovative Basic Research on High-Temperature Engineering using the HTTR; Present Status in the Netherlands of Research Relevant to High-Temperature Gas-cooled Reactor Design
Current Status of High-Temperature Engineering Research in FranceOverview of High-Temperature Reactor Engineering and Research; The Contribution of UK Organisations in the Development of New High-Temperature Reactors; SESSION II Improvement in Material Properties by High-temperature Irradiation; Improvement in Ductility of Refractory Metals by Neutron Irradiation; Effects of Superplastic Deformation on the Thernal and Mechanical Properties of 3Y-TZP Ceramics (Review); Development of an Innovative Carbon-based Ceramic Material: Application in High-Temperature, Neutron and Hydrogen Environment
A Carbon Dioxide Partial Condensation Cycle for High-Temperature ReactorsSESSION III Development of In-core Material Characterisation Methodsand Irradiation Facility; Development of the I-I Type Irradiation Equipment for the HTTR; Application of Optical Diagnostics in High-Temperature Gas-cooled Systems; Measurement Method of In-core Neutron and Gamma-ray Distributions with Scintillator Optical Fibre Detector and Self-Powered Detector; Development of In-core Test Capabilities for Material Characterisation
Application of Work Function Measuring Technique to Monitoring/Characterisation of Material Surfaces under IrradiationDevelopment of High-temperature Irradiation Techniques Utilising the Japan Materials Testing Reactor; SESSION IV Basic Studies on Behaviour of Irradiated Graphite/Carbon andCeramic Materials Including their Composites under both Operationand Storage Conditions; Investigation of High-Temperature Reactor (HTR) Materials; Radially Keyed Graphite Moderator Cores: An Investigation into the Stability of Finite Element Models
Understanding of Mechanical Properties of Graphite on the Basis of Mesoscopic Microstructure (Review)Advanced Graphite Oxidation Models; Arradiation Creep in Graphite - A Review; An Analysis of Irradiation Creep in Nuclear Graphites; Planning for Disposal of Irradiated Graphite: Issues for the New Generation of HTRs; Status of IAEA International Database on Irradiated Graphite Properties with Respect to HTR Engineering Issues; SESSION V Basic Studies on HTGR Fuel Fabrication and Performance; Evidence of Dramatic Fission Product Release from Irradiated Nuclear Ceramics
Method Reactor Tests of HTGR Fuel Elements at an Impulse Loading
In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, the NEA organised a Second Information Exchange Meeting on Basic Studies in the Field of High-temperature Engineering. These proceedings provide an overview of the activities being carried out in eight countries, the improvement of material properties for HTGR application, in-core monitoring methods and properties of irradiated graphite, and HTGR fuel fabrication and performance.
Gas cooled reactors -- Congresses.
Heat resistant materials -- Congresses.
High temperatures -- Congresses.
Nuclear Science